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Report No.
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Melting temperatures of oxide fuel for fast reactors

Kato, Masato

Melting temperatures of nuclear fuel are essential data to design the fuel pin. In this paper, the existing melting temperatures of the oxide fuels were reviewed, and the database of melting temperatures was made. In addition the effect of Pu content, MA content, oxygen-to-metal (O/M) ratio and burn-up on the melting temperatures were evaluated. The solidus temperatures of the oxide fuels were evaluated from the database. Average melting point of UO$$_{2}$$ was estimated to be 3133 K. Melting point of PuO$$_{2}$$ was obtained by evaluating the data of MOX with solid solution model and was estimated to be 2894 K. The solidus temperatures of MOX decreased with Pu content and to 3002 K at 40%Pu content.

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